Made available in DSpace on 2014-10-09T12:43:43Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:59Z (GMT). No. of bitstreams: 1 06645.pdf: 3401354 bytes, checksum: ff644fe657265b4b455934601c560694 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T10:38:01Z No. of bitstreams: 0 / Made available in DSpace on 2014-11-10T10:38:01Z (GMT). No. of bitstreams: 0 / O fosfogesso (FG), um subproduto da indústria de fosfato, é classificado como Material Radioativo de Ocorrência Natural Tecnologicamente Aumentado (TENORM) ou como um resíduo NORM. Ele é obtido durante o ataque da rocha fosfática com ácido sulfúrico para a produção de ácido fosfórico. O FG apresenta em sua composição radionuclídeos das séries de decaimento natural do U e Th: principalmente 226Ra, 228Ra, 232Th, 210Pb e 210Po. Os produtores brasileiros estocam o FG em pilhas secas, o que representa riscos para o meio ambiente. Sendo assim, estudos foram realizados para avaliar meios de sua reutilização. Uma possível solução para este problema é o emprego do FG na agricultura como um condicionador do solo. A entidade reguladora brasileira (CNEN) estabeleceu limites de isenção para o uso de FG na agricultura ou na indústria cimenteira: a concentração de atividade de 226Ra e 228Ra deve ser inferior a 1 Bq g-1. No entanto, para a sua aplicação segura, ainda é necessário assegurar que os radionuclídeos presentes no PG não estarão disponíveis para o ambiente. Este estudo tem como objetivo verificar a disponibilidade de 238U e 232Th em amostras de solos com FG através de percolação com água, por meio do cálculo da fração disponível. Esta fração foi obtida pela relação entre a concentração dos radionuclídeos no lixiviado (pelo emprego de um procedimento radioquímico adaptado, publicado pela Agência Internacional de Energia Atômica - IAEA) sobre a concentração total das amostras (obtida por Análise por Ativação com Nêutrons Instrumental e espectrometria gama). Os resultados demonstraram que a fração disponível dos radionuclídeos foi em todos os casos inferior a 0,2%. Isto indica que a utilização de fosfogesso como insumo agrícola não contribui para o aumento da disponibilidade de 238U e 232Th na água de lixiviação. / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

This thesis deals with the idea of using accelerator driven systems for thorium transmutation into the fissile material, which can be utilized in the accelerator driven systems and in thermal nuclear reactors. Thorium occurs on Earth only in fertile isotope Th-232. It can be converted to fissile U-233 by neutron capture and subsequent beta decay. The experimental part handles the data measured by the irradiation of four thorium samples by the secondary neutrons in the QUINTA spallation target, which was irradiated with 660~MeV protons. Reaction rates for the fission and spallation products were estimated using gamma spectroscopy and activation techniques. Furthermore, Pa-233 production rates were also determined in all experimental samples. Pa-233 and fission production rates were calculated in all experimental samples using the MCNPX transport code and evaluated nuclear data for high-energy reactions. The experimental results are of a great importance for the future investigation of thorium in the accelerator driven system concept, validation of Monte-Carlo based calculation codes and validation of high-energy nuclear models.

The Master Thesis deals with the use of thorium nuclear fuel in accelerator driven systems. Basic principle of ADS, present situation and future possibilities are described in this work. The main goal of the work is determination of neutron flux in spallation target QUINTA. In December 2013, an experiment was performed at Joint Institute for Nuclear Research, Dubna. Samples of cobalt, situated at different positions in QUINTA target, were irradiated in secondary neutron field generated by deuteron beam of energies 2 AGeV and 4 AGeV and beam of C-12 with energy 2 AGeV. The samples were measured with the use of germanium semiconductor detectors and analysed using gamma-ray spectrometry. Reaction rates of Co-59 products were determined. Neutron flux was determined in setup QUINTA on the base of experimental reaction rates. Experimental reaction rates were compared with calcula1tion of MCNPX code.

<p>  </p> <p>Actinide complexes have been targeted for their potential in group transfer applications. The study of these metals, such as thorium and uranium, is essential to better understand the reactions these metals are capable of facilitating.  Hydrotris(pyrazolyl)borates such as hydrotris(3,5-dimethylpyrazolyl)-borate (Tp*) and hydrotris(pyrazolyl)-borate (Tp) are superbulky, scorpionate ligands that have previously been used to synthesize novel uranium complexes and probe the reactivity of these materials. Similar thorium analogs have also been synthesized, but their reactivity has yet to be explored in great depth. Tp*ThCl3(THF) and Tp2ThCl2 have been reproduced and investigated as possible starting materials for such reactivity studies. While the former was found to be largely unreactive, the latter presents promising reactivity for the synthesis of thorium-element multiple bonds, and a novel thorium imido, Tp2Th(NDipp)(THF), has been synthesized and characterized using this scaffold. </p> <p><br></p> <p>The reactivity of a uranium tetrakis(imido), [U(NDipp)4][K2], has also been investigated to probe the prospect of group transfer reactions for potential catalysis applications in the future. An isocyanate, PhNCO, was reacted with this compound; the observed product showed that group transfer was incomplete, and a four-membered metallocycle product is likely formed instead. The synthesis of a novel thorium tris(imido) has also been targeted, and preliminary results are outlined. </p>

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Nuclear power plants provide about 11 percent of the world's electricity production. For fission process is uranium fuels used with varying percentage of enrichment 235U for most of nuclear reactors. Uranium reserves are reducing and their mining cost increases. Therefore, the thorium fuel is discussed as revolution fuel for current and future nuclear power plants. This diploma thesis deals with possibility of thorium fuel utilization at various types of nuclear reactors with a focus on light water reactors. The practical part of the thesis is focused on simulation and calculations of various uranium dioxide and thorium dioxide layers at the fuel rods. Model of WWER 440 reactor was developed for the calculations with the addition of thorium fuel. The model simulates burning out of fuel for 5 years, with monitoring of fuel behavior and tracking changes of each material. The thesis tries to define the suitable ratio and parameters of layers combination of uranium and thorium fuel. For these ratios and parameters the thesis tries to give sufficient amount of computational analyzes.

HOLCIM has various cement production plants across India. These plants struggle to produce the projected amount of cement due to electricity shortages. Although coal is abundant in India, the production thereof is in short supply. It is proposed that a thorium HTR (100 MWt) combined with a PCU (Rankine cycle) be constructed to supply a cement production plant with the required energy. The Portland cement production process is investigated and it is found that process heat integration is not feasible. The problem is that for the feasibility of this IPP to be assessed, a Rankine cycle needs to be adapted and optimised to suit the limitations and requirements of a 100 MWt thorium HTR. Advantages of the small thorium HTR (100 MWt) include: on-site construction; a naturally safe design and low energy production costs. The reactor delivers high temperature helium (750°C) at a mass flow of 38.55 kg/s. Helium re-en ters the reactor core at 250°C. Since the location of the cement production plant is unknown, both wet and dry cooling tower options are investigated. An overall average ambient temperature of India is used as input for the cooling tower calculations. EES software is used to construct a simulation model with the capability of optimising the Rankine cycle for maximum efficiency while accommodating various out of the norm input parameters. Various limitations are enforced by the simulation model. Various cycle configurations are optimised (EES) and weighed against each other. The accuracy of the EES simulation model is verified using FlowNex while the optimised cycle results are verified using Excel’s X-Steam macro. It is recommended that a wet cooling tower is implemented if possible. The 85% effective heat exchanger delivers the techno-economically optimum Rankine cycle configuration. For this combination of cooling tower and heat exchanger, it is recommended that the cycle configuration consists of one de-aerator and two closed feed heaters (one specified). After the Rankine cycle (PCU) has been designed and optimised, it is evident that the small thorium HTR (100 MWt) can supply the HOLCIM plant with the required energy. The optimum cycle configuration, as recommended, operates with a cycle efficiency of 42.4% while producing 39.867 MWe. A minimum of 10 MWe can be sold to the Indian distribution network at all times, thus generating revenue. / MIng (Mechanical Engineering), North-West University, Potchefstroom Campus, 2014

HOLCIM has various cement production plants across India. These plants struggle to produce the projected amount of cement due to electricity shortages. Although coal is abundant in India, the production thereof is in short supply. It is proposed that a thorium HTR (100 MWt) combined with a PCU (Rankine cycle) be constructed to supply a cement production plant with the required energy. The Portland cement production process is investigated and it is found that process heat integration is not feasible. The problem is that for the feasibility of this IPP to be assessed, a Rankine cycle needs to be adapted and optimised to suit the limitations and requirements of a 100 MWt thorium HTR. Advantages of the small thorium HTR (100 MWt) include: on-site construction; a naturally safe design and low energy production costs. The reactor delivers high temperature helium (750°C) at a mass flow of 38.55 kg/s. Helium re-en ters the reactor core at 250°C. Since the location of the cement production plant is unknown, both wet and dry cooling tower options are investigated. An overall average ambient temperature of India is used as input for the cooling tower calculations. EES software is used to construct a simulation model with the capability of optimising the Rankine cycle for maximum efficiency while accommodating various out of the norm input parameters. Various limitations are enforced by the simulation model. Various cycle configurations are optimised (EES) and weighed against each other. The accuracy of the EES simulation model is verified using FlowNex while the optimised cycle results are verified using Excel’s X-Steam macro. It is recommended that a wet cooling tower is implemented if possible. The 85% effective heat exchanger delivers the techno-economically optimum Rankine cycle configuration. For this combination of cooling tower and heat exchanger, it is recommended that the cycle configuration consists of one de-aerator and two closed feed heaters (one specified). After the Rankine cycle (PCU) has been designed and optimised, it is evident that the small thorium HTR (100 MWt) can supply the HOLCIM plant with the required energy. The optimum cycle configuration, as recommended, operates with a cycle efficiency of 42.4% while producing 39.867 MWe. A minimum of 10 MWe can be sold to the Indian distribution network at all times, thus generating revenue. / MIng (Mechanical Engineering), North-West University, Potchefstroom Campus, 2014